An experimental program was carried out to evaluate the validity of using the cesium-137 content of coating waste as an indirect measure of the uranium and/or plutonium content. A small number of large volume samples and a large number of normal (small volume) samples of Redox and Purex coating waste were used for the investigations. The distribution of cesium, uranium, and plutonium throughout the two-phase system was determined. a comparison of uranium by direct assay and uranium by cesium-137 was obtained for both Redox and Purex samples. A plant test was carried out to determine the extent of cesium migration and the extent to which product materials are transferred from the dissolver to underground storage in coating waste. Sampling for cesium-137 was found to be markedly more consistent than for product materials. In general, the cesium-137 content was found to be a more sensitive measure of the relative product content of coating waste than the uranium content as measured by direct assay. To date al the evidence indicates that the cesium-137 content of coating waste is a valid measure of the product content. However, more ``back-up`` data and a ``routine use`` evaluation are needed before the method can be considered …

As a result of the evaporation explosion in the Radiochemical Processing Pilot Plant on Nov. 20, 1959, two cells were contaminated with plutonium to a transferable level of 10/sup 8/ d/m/100 sq cm. The area involved measures 40 by 20 by 27 ft high with a total surface area, including equipment, of 10,000 sq ft. The cells were decontaminated by a factor of 1000 in five months by removing loose equipment, debris, and shielding blocks and flushing with 430,600 liters of various decontaminating reagents. The remaining contamination (10/sup 4/ - 10/ sup 5/ d/-m/100 sq cm) was fixed to the surface with three coats of paint. The general beta-gamma radiation background was decreased from 2000 to 30 mr/hr and the long-lived alpha contamination in the air was reduced from 2 x 10/sup -10/ to 8 x 10/sup -13/ mu c/cc. Approximately 141 g of plutonium was flushed from the cell surfaces. The total direct effort expended was 3000 man-hr including 250 entries into the cell, 175 of which were made in plastic air suits. There were no overexposares from beta-gamma radiation and no detectable increase in the body burden of plutonium of any individual involved. (auth)

Development of a direct coupled, transistorized current amplifler is reported with sensitivities extending below the millimicroampere region of input currents. The amplifier employs a shunt feedback and exhibits reproducible characteristics. Discovery of this special effect and the design and testing employed in the incorporation of transistors into the amplifier are described. (J.R.D.)

Continuous dissolution of Zircaloy-2 in a titanium dissolver appears practical using as a dissolvent refluxing 3 M HNO/sub 2/-l.2 M HF--0.4 M HBF/sub 4/-0.6 M Cr(III)-0.4 M Cr(VI)--0.46 M Zr. Dissolution and corrosion rates were 10 mg/cm/sub 2/-min and 0.0 mil/mo in short term tests, respectively. A stable product solution containing 0.36 M Zr was obtained after addition of aluminum nitrate to complex fluoride ion. Another reagent investigated for use in continuous dissolution was 16 M HNO/sub 3/-2.6 M F-0.025 M HBF/sub 4/-1.4 M Zr with short term titanium corrosion rates of 0.0 mil/mo. However, Zircaloy-2 dissolution rates were only 3 mg/cm/sup 2/-min in the latter reagent. (auth)

Neutron and gamma penetrations through and behind BeO were measured. Neutron spectra measurements by threshold foil techniques indicated practically no change in the fast-neutron spectrum above 2.5 Mev in BeO. Thus, beryllium appears to lie in the transition region between the very light elements that harden a fission spectrum and the heavier elements that soften it. The ratio of fast-neutron fluxes below and above 2.5 Mev increased rapidly with distance through the BeO. Information indicated that the flux peaked at around 1.5 to 2.5 Mev. In this energy range the scattering cross section of beryllium goes through a minimum. Fast neutron dose measurements through BeO were compared with those calculated by the moments method. The removal cross section for BeO was determined from fast-neutron dose rates measured in the water behind the slabs. Gamma dose rates were measured through and be hind the BeO slabs with a carbon chamber. The gamma dose rate decreased with a relaxation length of about 11 cm near the source. The relaxation length increased with distance through BeO, indicating spectrum hardening. Gamma spectra were measured at intervals behind BeO slabs with a collimated sodium icdide crystal. The 6.8 and 3.41 Mev beryllium capture gamma rays …

At the request of B-C Maintenance Engineering, this study was initiated to investigate the feasibility of replacing the 190-C and 105-C process water flow-meter orifices with venturi tubes. Specific aspects of the problem studied were potential flow increases, accompanying production increases, costs, and the ability of the existing 190-C pumps and motors to provide the potential flow increase.

The rail shipment of large quantities of radiocesium involves a potential accidental release of this material in a readily available form to the biosphere. The magnitude of the associated potential damage to man and his environment is evaluated in this report. The evaluation of the consequences of an accidental release of Cs-137 from the Shielded Transfer Tank, Model II (STT) assumes loss of Cs-137 to the atmosphere or to surface-water. Release to the atmosphere could result from a collision followed by fire or explosion. In the event of a fire, a small fraction of the Cs-137 vould be volatilized. An explosion would disperse the Cs-137 still adsorbed to Decalso as particulates. In either case, the material is assumed to be dispersed by atmospheric mechanisms which can be described by modified Sutton equations. The accident involving a fire or explosion assumes that 1 percent or 10 percent, respectively, of 90,000 curies of Cs-137 is dispersed in a metropolitan area. Contamination of the surrounding suburban area is also involved. Damage estimates amount to about 60 million dollars and 400 million dollars, corresponding to a 1 percent and a 10 percent release respectively. Another possible type of accident involves the release of the …

The homogeneous decomposition of H/sub 2/O/sub 2/ by HNO/sub 3/, and by HNO/sub 3/ solutions (>1M) containing Pu(IV); Pu(IV) and Pt; Pu(IV) with Cu(II) and Fe(III); and Pu(IV) with Pt, Cu(II), and Fe(III) as a function of temperature is investigated. The range of STAH/sub 2/O/sub 2/! is 10/sup -2/ to 10/sup -1/M, and STAPu(IV)! p 1.25M. The evolution of gas is first order in all cases up to STAHNO/sub 3/! approximately 10M. Above STAHNO/sub 3/! approximately 10M, the reaction is no longer first order. Approximate activation energies for the decomposition of H/sub 2/O/sub 2/ by the various catalysts are listed. (auth)

The dynamic (gas saturation) method was used to determine upper and lower limits for the dissociation pressure of the complex formed when MoF/sub 6/ is absorbed by NaF. The limits were 0.4 to 4.6 mm Hg at 100 deg C and 8.4 to 27 mm Hg at 150 deg C. A lower limit, 64 mm Hg, was determined at 200 deg C. As a check on the method the dissociation pressure of the complex UF/sub 6/ - (NaF)/ sub 3/ was determined at 100, 200, and 240 deg C. The measured values were in satisfactory agreement with accepted values of dissociation pressure for this compound. (auth)

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It is almost sixty years since Emil Fischer was describing on a platform such as this one some of the work which led to the basic knowledge of the structure of glucose and its relatives. Today we will be concerned with a description of the experiments which have led to a knowledge of the principal reactions by which those carbohydrate structures are created by photosynthetic organisms from carbon dioxide and water, using the energy of light. The speculations on the way in which carbohydrate was built from carbon dioxide began not long after the recognition of the basic reaction and were carried forward first by Justus von Liebig and then by Adolf von Baeyer and, finally, by Richard Wilstatter and Arthur Stoll into this century. Actually, the route by which animal organisms performed the reverse reaction, that is, the combustion of carbohydrate to carbon dioxide and water with the utilization of the energy resulting from this combination, turned out to be the first one to be successfully mapped, primarily by Otto Meyerhoi and Hans Krebs. Our own interest in the basic process of solar energy conversion by green plants began some time in the years between 1935 and 1937, during …

The phase equilibrium relations for the systems limiting the quaternary system LiF--BeF/sub 2/--UF/sub 4/--ThF/sub 4/ are described in detail, along with available information on the quaternary system itself. The implications of the extensive solid solutions in the limiting systems are discussed, and experimental information supporting the conclusions is presented. The optical properties, crystallographic properties, and x-ray diffraction patterns for the phases occurring in these systems are tabulated. Specific compositions of project interest to which references have been made in the ORNL literature are given special attention. Reference is made to literature reporting properties of these materials other than those discussed in this report. (auth)

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The C reactor is presently, operating with all process water discharging through one downcomer. Pressure measurements at the downcomer lid show the top tray is nearly flooded, thus prohibiting further flow increases until the downcomer is modified or both downcomers are used simultaneously. Operation with two downcomers can result in two sources of error in the power calculation: (1) Errors in measured outlet temperature can occur, apparently due to the increased venting capacity. The magnitude of the effect is probably unpredictable and could not be compensated for in the power calculation. Since the temperature error occurs only downstream of the downcomer vents, the logical solution is to move the outlet temperature devices to the risers. The method of administering bulk temperature limits will have to be changed to account for the thermal shield flow entering downstream of the outlet thermohms. (2) Simultaneous flow and temperature unbalances can result in power calculation errors since there is no way of knowing the actual flow through each downcomer. It is assumed that the power calculation would have to be made from the total flow and the average of the two outlet temperatures. The primary purpose of this study was to determine whether the …

An evaluation of two thin-walled outer tubes showed that more extensive alpha working of the billet core stock results in more uniform cladding on the extruded tube. In an effort to eliminate breakthrough and to reduce eccentricity, shift, and bending of the mandrel, two experimental coppernickel billets with Zircaloy sleeves were extruded to check a modified billet design. lt was observed that the final grain size of the unalloyed uranium core of a thin- walled outer tube is insensitive to small variations in the cooling rate from the beta-treatment temperature. An axia' load of 3000 pounds applied to a thin- walled outer tube during autoclaving was ineffective in preventing bowing of the tube. Shipping experiments demonstrated that current packaging methods of thin- walled inner tubes do not prevent bowing during transit. The fabrication of specimens for the capsule irradiation program was concluded with the shipment of sixteen specimens and excess extruded tube stock to Savannah River Laboratory. The following core compositions were represented: U-1 wt.% Si, unalloyed dingot uranium, U-0.3 wt.% Al-0.5 wt.% Si, and U-0.3 wt.% Cr-0.3 wt.% Mo. All irradiation specimens were supplied in the beta-treated condition. The mechanical behavior of Zircaloy-4-clad dingot uranium tube sections was evaluated …

The power calculator at C Reactor and the process pump flowmeters at 190-C use orifice plates as primary sensing elements. These orifices were designed for considerably less flow and at the present higher flows, the reactor riser pressure is appreciably reduced as the result of the inefficiency of the orifices. Only a portion of the differential pressure across an orifice is recovered. The amount is dependent upon the ratio of the orifice diameter to pipe diameter. The permanent loss across these two orifices is 16 psi. The permanent pressure loss resulting from properly sized venturi elements would be 1.6 psi, for a resultant decrease in system pumping resistance of 14 to 15 psi. This would permit higher process water flow and reactor power levels.

The objective of this supplement to PT-IP-376-D, Irradiation of MGCR-HDR-3 Test Element is to authorize 1000 hours of operation at a maximum test specimen surface temperature of 1700 F. The original production test authorized a test duration of four months at a maximum specimen surface temperature of 1500 F; supplement A authorized extension of the test duration to ten months. The desired increase in surface temperature is requested to demonstrate the general feasibility of operation of the fuel element at 1700 F, and to obtain specific information on the performance of Hastelloy-X cladding and fuel bodies. The increased temperature has been approved by the Atomic Energy Commission.

The objective of this production test is to authorize the installation of at least 40 additional large size Zircaloy process tubes in graphite channels that have been enlarged to 2.275 inches at C Reactor and to charge these tubes with large diameter (CVIN) fuel elements to obtain preliminary conversion ratio data and further qualitative data regarding the irradiation behavior of large diameter fuel element designs.

The distribution of small amounts of radioactive Cu, Ag, and Au between precipitates of these elements and their solutions in bismuth was investigated at different temperatures by sampling the liquid. In all cases the . Doerner-Hoskins law was obeyed. Approximate distribution ratios were calculated and plotted against 1/T. Extrapolation to the melting temperature of the major component X in these Bi-X-Y systems yields values which compare well with the distribution constants obtained either from the binary X-Y phase diagrams or with those calculated from thermodynamic data. The data support solid solution formation as the mechanism of coprecipitation. This investigation also suggests a new method of obtaining significant portions of solidus curves.

The liquidus curves of the Bi-Cu, Bi-Ag, and Bi-Au systems were re- determined by means of a sampling method. The Bi-Ag curve,was somewhat shifted from the previously determined location. The eutectic was found at 262.5 {+-} 0.2{degrees}C at 4.95 {+-} 0.05 atom % silver (2.62 wt %). The Bi-Cu liquidus agreed fairly well with Kleppa's data over the range investigated by him. The discrepancies in the literature in regard to higher copper concentrations were resolved. The.eutectic was determined to be at 270.6 {+-} 0.1{degrees} C at 0.46 atom % copper(0.14 wt % ). The Bi-Au liquidus did not agree well with the few experimental data available. Below the peritectic temperature, a completely new liquidus curve was established. The peritectic.was found to be at 371 {+-} 2{degrees} C by.means.of differential thermal analysis. The composition is 23.1 atom % gold (24.1 wt %). The eutectic is at 13.4 {+-} 0.2 atom % gold (14.1 wt %) at.241.5 {+-} 0.5{degrees}C.

Current Practice -- A patrolman observes river traffic 24 hours a day, seven days a week, from a 50 foot enclosed tower located on the bank of the river. Under normal daylight conditions the opposite shore line and bluffs (2,000`) and approximately three miles both up and down the river can be seen by naked eye with close up identification obtained through use of field glasses. For night time operation a manually operated searchlight is used to sweep the river for moving or floating objects. Proposal -- To determine whether it is feasible to replace the patrolman in the river tower with a remotely controlled closed circuit television and searchlight system.

Each tube of the PRTR is provided with flow monitoring equipment consisting of a venturi flow meter in the inlet piping, sensing lines containing valves, and a Panellit flow transmitter. The flow transmitter does three things: converts the pressure drop signal of the venturi to a visual readout; provides an electrical signal for recording; and provides a signal to the safety circuit which causes a reactor scram should the flow increase or decrease beyond pre-set valves. After startup of the PRTR, it was found that the readings of flow meters on those process tubes which connect near the inlet of the bottom ring headers were fluctuating excessively. As an interim measure during the power tests at low reactor powers, the meter fluctuations were reduced by throttling the valves in the sensing lines from the flow venturi to the flow meter. This was recognized as being questionable for a permanent solution since this practice introduces an unknown and variable lengthening of the response characteristics of the meter. An experimental program was therefore undertaken to determine the degree of valve throttling which might be appropriate for fluctuation suppression and to device other and better methods of suppression. The experiments show that throttling …